Safeguards in the prototype fast breeder reactor MONJU
Creators
- 1. Power Reactor and Nuclear Fuels Development Corporation, Ibaraki-ken (Japan)
Description
MONJU is a prototype fast breeder reactor in Japan designed to have a 280-MW(electric) output. The Power Reactor and Nuclear Fuel Development Corporation (PNC) started its construction in the autumn of 1985 in Tsuruga. The loading of the core fuel assemblies was started in October 1993, and the preoperational test is ongoing. MONJU uses 198 mixed-oxide (MOX) fuel assemblies as core fuel and 172 depleted uranium assemblies as blanket fuel. Assemblies loaded in-core and stored in the ex-vessel storage tank (EVST) reside in liquid sodium. These plutonium-containing fuel assemblies, MOX, and irradiated depleted uranium are regarded as in the difficult-to-access area, and the flows of fuel assemblies into and out of the area must be verified. Flow is verified by fuel flow monitors measuring radiation, which can limit inspector attendance during fuel handling
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 72
- Journal Issue
- Suppl.1
- Journal Page Range
- p. 6.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 5. international American Nuclear Society (ANS) conference.
- Dates
- 24-29 Sep 1995.
- Place
- Jackson Hole, WY (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27046002
- Subject category
- S98: NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MONJU REACTOR; NUCLEAR MATERIALS MANAGEMENT; SAFEGUARDS
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MANAGEMENT; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-9509215--.